64-Gd-154
Spin
Level energy(keV) Spin & Parity
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ground state 0+
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
153.920874060 ± 0.000001747 (amu) [mass excess = -73705.338 ± 1.628 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-3549.651 ± 45.298 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Gd-154.
Figures of cross sections, Gd-154: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Gd-153 (Z= 64, A=153), MT=102 (n,γ)
Gd-154 (Z= 64, A=154), MT= 2 (Elastic scattering)
Gd-154 (Z= 64, A=154), MT= 4 (Inelastic scattering)
Gd-155 (Z= 64, A=155), MT= 16 (n,2n)
Gd-156 (Z= 64, A=156), MT= 17 (n,3n)
Dy-156 (Z= 66, A=156), MT=106 (n,3He)
Dy-158 (Z= 66, A=158), MT= 22 (n,nα)
Dy-159 (Z= 66, A=159), MT= 24 (n,2nα)
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Gd-154 U-235 Thermal 1.118220e-13 7.156600e-14
Gd-154 U-235 Fast 2.574690e-14 1.647800e-14
Gd-154 U-235 High 6.839380e-09 4.377190e-09
Gd-154 U-238 High 2.903160e-12 1.858030e-12
Gd-154 Pu-239 Thermal 9.258550e-11 5.925470e-11
Gd-154 Pu-239 Fast 2.019670e-10 1.292590e-10
Gd-154 Pu-239 High 4.673030e-07 2.990740e-07
Gd-154 Pu-241 Thermal 7.911270e-14 5.063220e-14
Gd-154 Pu-241 Fast 8.223820e-13 5.263240e-13
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Gd-154 U-235 Thermal 1.936640e-09 1.239450e-09
Gd-154 U-235 Fast 6.196220e-10 3.965580e-10
Gd-154 U-235 High 3.020370e-06 1.926210e-06
Gd-154 U-238 Fast 8.251430e-11 1.382920e-14
Gd-154 U-238 High 1.952030e-08 1.248010e-08
Gd-154 Pu-239 Thermal 2.799920e-07 1.791950e-07
Gd-154 Pu-239 Fast 4.720310e-07 3.021000e-07
Gd-154 Pu-239 High 5.543240e-05 3.546240e-05
Gd-154 Pu-241 Thermal 3.069960e-09 1.964780e-09
Gd-154 Pu-241 Fast 1.258880e-08 8.056860e-09
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data